Development of a thermal-hydraulic analysis code for CARR |
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| Affiliation: | 1. State key laboratory of Multi Phase Flow in Power Engineering, Xi’an Jiaotong University, Xi’an, Shaanxi 710049, PR China;2. Department of Nuclear and Thermal Power Engineering, Xi’an Jiaotong University, Xi’an, Shaanxi 710049, PR China;1. School of Mechanical Engineering, Pusan National University, Busan, South Korea;2. Korea Atomic Energy Research Institute (KAERI), Daejon, South Korea;1. Nuclear Research and Consultancy Group NRG, Petten, The Netherlands;2. Delft University of Technology, Delft, The Netherlands;1. Oak Ridge National Laboratory, Building 5700, MS-6165 Oak Ridge, TN 37830, USA;2. The Pennsylvania State University, 229 Reber Building, University Park, PA 16802, USA;1. Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety, Ministry of Education, Tsinghua University, Beijing 100084, China;2. School of Engineering, RMIT University, Melbourne, VIC 3083, Australia;1. Oak Ridge National Laboratory, One Bethel Valley Rd., Oak Ridge, TN 37831, United States;2. Department of Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor, MI 48109, United States |
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| Abstract: | The China advanced research reactor (CARR) being built in Beijing, China, is a multipurpose research reactor for a variety of fields. Theoretical calculation of thermal hydraulic characteristics of CARR is presented in this paper. The theoretical analysis consists of initial steady and transient accidental analyses. Point reactor neutron kinetics model with six groups of delayed neutron is adopted for the solution of reactor power. All possible flow and heat transfer conditions are considered and the corresponding optional models are supplied in the theoretical calculations. A new simple and convenient model is proposed for the resolution of the transient behaviors of main pump instead of the complicated four-quadrant model. Gear method and Adams predictor–corrector method are adopted alternately for a better solution to such ill-conditioned differential equations corresponding to detail process. The initial multi-channel analysis shows that the effects of geometrical size on flow distribution play dominant role and the effects of core power distribution may be neglected. The temperature fields of fuel elements under asymmetrical cooling condition are also obtained, which are the bases for further study on transient-induced stress analysis, etc. Accidental analyses show that the activity of emergency cooling system apparently reduces the peak temperatures of fuel and coolant, peak quality and other operation parameters. Thus it effectively ensures the safety in operation of CARR. Because of the adoption of modular programming techniques, this code is expected to be applied to accidental analysis of other types of reactors by easily modifying the corresponding function modules. Also, this code is expected to be validated against experimental data. |
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